Paper Title:
Effects of Pb on SCC of Alloy 600 and Alloy 690 in Prototypical Steam Generator Chemistries
  Abstract

Intergranular attack/stress corrosion cracking of Alloy 600 continues to be an issue in the tube/tube support plate crevices and top of tubesheet locations of recirculating steam generators and in the upper bundle of free span superheated regions of once through steam generators (OTSG). Recent examinations of degraded pulled tubes from several plants suggest possible lead involvement in the degradation. Laboratory investigations have been performed to determine the factors influencing lead cracking in Alloy 600 and Alloy 690 steam generator tubes. The test environment is believed to be prototypical, with the addition of lead oxide, of a concentrated liquid phase existing in the pores of thin deposits on upper bundle tubes of an OTSG. Highly strained reverse U-bend specimens were tested at controlled electrochemical potentials. Maximum susceptibility was at open circuit potential, unlike cracking of Alloy 600 in caustic and acid sulfate environments where maximum susceptibility occurs when specimens are polarized above the open circuit potential. Transgranular, intergranular and mixed mode cracking was observed and in all Alloy 600 conditions tested (mill annealed, sensitized, thermally treated) while thermally treated Alloy 690 has so far resisted cracking. A film rupture/anodic dissolution model with displacement plating of Pb preceding passive film formation is consistent with the experimental observations

  Info
Periodical
Materials Science Forum (Volumes 475-479)
Main Theme
Edited by
Z.Y. Zhong, H. Saka, T.H. Kim, E.A. Holm, Y.F. Han and X.S. Xie
Pages
1387-1392
DOI
10.4028/www.scientific.net/MSF.475-479.1387
Citation
J. Lumsden, A. McIlree, R. Eaker, R. Thompson, S. Slosnerick, "Effects of Pb on SCC of Alloy 600 and Alloy 690 in Prototypical Steam Generator Chemistries", Materials Science Forum, Vols. 475-479, pp. 1387-1392, 2005
Online since
January 2005
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$32.00
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